CSRL-V: an ENDF/B-V 227-Group Cross Section Library for Criticality Safety Studies
Conference
·
OSTI ID:5363057
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Union Carbine Nuclear Division
The AMPX system was used to generate a P3 227-neutron-group master cross-section library containing data for all materials in the ENDF/B-V general purpose file. CSRL-V is a data base for the subsequent generation of problem-dependent fine- and/or broad-group cross sections for shipping cask calculations and other criticality safety analyses. The problem-dependent data can be used with codes such as KENO IV, ANISN, XSDRNPM, VENTURE, DOT, MORSE, etc. CSRL-V data can be coupled with photon-production and photon-interaction multigroup data produced with the AMPX system to produce coupled neutron-gamma cross-section libraries. Consideration was given to the resonance structure of prominent nuclei, the thresholds of important reactions, and various fission spectra. Data in the CSRL-V library were checked for first-order consistencies and tested in performance parameter calculations for a series of benchmark critical experiments. The CSRL-V library is available on magnetic tape.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Union Carbine Nuclear Division
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USNRC, Office of Nuclear Material Safety and Safeguards
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5363057
- Report Number(s):
- CONF-800607--41
- Country of Publication:
- United States
- Language:
- English
Similar Records
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CSRL-V ENDF/B-V 227-Group Neutron Cross-Section Library and Its Application to Thermal-Reactor and Criticality Safety Benchmarks
CSRL-V: processed ENDF/B-V 227-neutron-group and pointwise cross-section libraries for criticality safety, reactor, and shielding studies
Technical Report
·
Sat Sep 01 00:00:00 EDT 1990
·
OSTI ID:6502303
CSRL-V ENDF/B-V 227-Group Neutron Cross-Section Library and Its Application to Thermal-Reactor and Criticality Safety Benchmarks
Conference
·
Mon May 17 00:00:00 EDT 1982
·
OSTI ID:5236157
CSRL-V: processed ENDF/B-V 227-neutron-group and pointwise cross-section libraries for criticality safety, reactor, and shielding studies
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5334128
Related Subjects
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
AMPX Master Cross-Section Library
ANISN
CRITICALITY
CROSS SECTIONS
DOT
Evaluated Nuclear Data File (ENDF)
Fission Spectra
Hansen-Roach Energy Structures
KENO IV
MORSE
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
P3-APPROXIMATION
RADIATION TRANSPORT
SPHERICAL HARMONICS METHOD
TRANSPORT THEORY
VENTURE
XSDRNPM
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
AMPX Master Cross-Section Library
ANISN
CRITICALITY
CROSS SECTIONS
DOT
Evaluated Nuclear Data File (ENDF)
Fission Spectra
Hansen-Roach Energy Structures
KENO IV
MORSE
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
P3-APPROXIMATION
RADIATION TRANSPORT
SPHERICAL HARMONICS METHOD
TRANSPORT THEORY
VENTURE
XSDRNPM